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Title: Fuel cladding temperature predictions for LOFT LOCE Ll-5. [PWR]

Abstract

Fuel cladding temperature predictions were performed for loss-of-fluid test (LOFT) loss-of-coolant experiment (LOCE) L1-5 using the RELAP4 computer code. Two versions of this code were used, RELAP4/MOD5 and RELAP4/MOD6. Measured thermocouple data have been compared to these predictions to determine the relative accuracy of the two RELAP4 computer code versions and their respective blowdown heat transfer correlations selected to describe the fuel cladding surface temperature response during the subcooled and saturated blowdown phase of the LOCE. LOFT LOCE L1-5 simulated a 200% double-ended offset shear break in the cold leg of a four-loop large pressurized water reactor (LPWR). The initial conditions for the LOCE were: zero power with a nuclear core installed, primary coolant (PC) temperature of 541 K, PC pressure of 15.6 MPa, and PC flow of 176 Kg/sec. The PC pumps were running until the end of the blowdown phase of the LOCE, and cold leg emergency core coolant (ECC) injection initiated at 19 seconds.

Authors:
;
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls (USA)
OSTI Identifier:
6607046
Report Number(s):
CONF-781105-2
TRN: 79-001136
DOE Contract Number:  
EY-76-C-07-1570
Resource Type:
Conference
Resource Relation:
Conference: ANS meeting, Washington, DC, USA, 12 Nov 1978; Other Information: Portions of document are illegible
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LOFT REACTOR; REACTOR EXPERIMENTAL FACILITIES; LOSS OF COOLANT; HEAT TRANSFER; SIMULATION; PWR TYPE REACTORS; FUEL CANS; TEMPERATURE DISTRIBUTION; TEMPERATURE GRADIENTS; ACCIDENTS; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Perryman, J L, and White, J R. Fuel cladding temperature predictions for LOFT LOCE Ll-5. [PWR]. United States: N. p., 1978. Web.
Perryman, J L, & White, J R. Fuel cladding temperature predictions for LOFT LOCE Ll-5. [PWR]. United States.
Perryman, J L, and White, J R. 1978. "Fuel cladding temperature predictions for LOFT LOCE Ll-5. [PWR]". United States. https://www.osti.gov/servlets/purl/6607046.
@article{osti_6607046,
title = {Fuel cladding temperature predictions for LOFT LOCE Ll-5. [PWR]},
author = {Perryman, J L and White, J R},
abstractNote = {Fuel cladding temperature predictions were performed for loss-of-fluid test (LOFT) loss-of-coolant experiment (LOCE) L1-5 using the RELAP4 computer code. Two versions of this code were used, RELAP4/MOD5 and RELAP4/MOD6. Measured thermocouple data have been compared to these predictions to determine the relative accuracy of the two RELAP4 computer code versions and their respective blowdown heat transfer correlations selected to describe the fuel cladding surface temperature response during the subcooled and saturated blowdown phase of the LOCE. LOFT LOCE L1-5 simulated a 200% double-ended offset shear break in the cold leg of a four-loop large pressurized water reactor (LPWR). The initial conditions for the LOCE were: zero power with a nuclear core installed, primary coolant (PC) temperature of 541 K, PC pressure of 15.6 MPa, and PC flow of 176 Kg/sec. The PC pumps were running until the end of the blowdown phase of the LOCE, and cold leg emergency core coolant (ECC) injection initiated at 19 seconds.},
doi = {},
url = {https://www.osti.gov/biblio/6607046}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1978},
month = {1}
}

Conference:
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